NEA-1858 IFPE/CANDU-FIO-130.
IFPE/CANDU-FIO-130, CANDU experiment FIO-130 Fuel Behaviour under LOCA Conditions
NAME OF EXPERIMENT, COMPUTER, DESCRIPTION OF EXPERIMENT, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/CANDU-FIO-130 | NEA-1858/01 | Arrived | 23-JUN-2010 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1858/01 | Many Computers |
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3. DESCRIPTION OF EXPERIMENT
The EXP-FIO-130 experiment, performed in the NRX (National Research Experimental) reactor at the Chalk River Laboratories in 1983, was a part of an experimental program on fuel performance under high-temperature transient conditions such as those associated with the onset of a loss-of-coolant accident (LOCA).
The NRX was a heavy-water moderated, light-water cooled reactor with a graphite neutron reflector. NRX had two in-reactor loops, X-2 and X-4, which were used as experimental facilities. Low- and high-pressure experiments could be performed in NRX using a flow tube designed to use the normal reactor cooling system.
The main purpose of the EXP-FIO-130 experiment was to provide quantitative code validation data and information on the thermal and mechanical behaviour of Zircaloy-sheathed UO2 fuel elements during LOCA conditions.
An instrumented, Zircaloy-sheathed UO2 fuel element assembly, previously irradiated to a burnup of 32 MWh/kgU and average linear power of 50 kW/m during a soak irradiation phase, was subjected to a coolant depressurization (blowdown) transient in the X-2 pressurized water loop of the NRX reactor. The fuel element used 1.3 wt% U-235 in uranium dioxide fuel clad with Zircaloy-4 sheath material.
The fuel assembly was instrumented with thermocouples for the fuel, fuel sheath and coolant, pressure transducers for element internal and coolant pressures, and a flux detector. The instrumentation provided data throughout the soak irradiation and subsequent blowdowns.
Post-irradiation examination (PIE) of the fuel element assembly included visual examination, photography, sheath profilometry measurements, neutron radiography, and Metallography, including fuel grain size measurements. Chemical burnup and fission-gas measurements were not acquired.
Another in-reactor LOCA experiment, the EXP-FIO-131 experiment, was conducted in 1983, using a similar, unirradiated, fuel element.
The purpose of conducting the same test on both an irradiated element (EXP-FIO-130) and an unirradiated element (EXP-FIO-131) was to demonstrate that irradiation has a negligible effect on high-temperature sheath strain.
The EXP-FIO-130 experiment, performed in the NRX (National Research Experimental) reactor at the Chalk River Laboratories in 1983, was a part of an experimental program on fuel performance under high-temperature transient conditions such as those associated with the onset of a loss-of-coolant accident (LOCA).
The NRX was a heavy-water moderated, light-water cooled reactor with a graphite neutron reflector. NRX had two in-reactor loops, X-2 and X-4, which were used as experimental facilities. Low- and high-pressure experiments could be performed in NRX using a flow tube designed to use the normal reactor cooling system.
The main purpose of the EXP-FIO-130 experiment was to provide quantitative code validation data and information on the thermal and mechanical behaviour of Zircaloy-sheathed UO2 fuel elements during LOCA conditions.
An instrumented, Zircaloy-sheathed UO2 fuel element assembly, previously irradiated to a burnup of 32 MWh/kgU and average linear power of 50 kW/m during a soak irradiation phase, was subjected to a coolant depressurization (blowdown) transient in the X-2 pressurized water loop of the NRX reactor. The fuel element used 1.3 wt% U-235 in uranium dioxide fuel clad with Zircaloy-4 sheath material.
The fuel assembly was instrumented with thermocouples for the fuel, fuel sheath and coolant, pressure transducers for element internal and coolant pressures, and a flux detector. The instrumentation provided data throughout the soak irradiation and subsequent blowdowns.
Post-irradiation examination (PIE) of the fuel element assembly included visual examination, photography, sheath profilometry measurements, neutron radiography, and Metallography, including fuel grain size measurements. Chemical burnup and fission-gas measurements were not acquired.
Another in-reactor LOCA experiment, the EXP-FIO-131 experiment, was conducted in 1983, using a similar, unirradiated, fuel element.
The purpose of conducting the same test on both an irradiated element (EXP-FIO-130) and an unirradiated element (EXP-FIO-131) was to demonstrate that irradiation has a negligible effect on high-temperature sheath strain.
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NEA-1858/01, included references:
- P.J. Fehrenbach, J.A. Walsworth, R. C. Spencer, W.R. Chase and R. D. Delaney:"In-Reactor LOCA Tests of Zircaloy-Sheathed UO2 Fuel at Chalk River", AECL
Report AECL-8974, June 1985, Proceedings of 6th CNS Annual Conference, June
1985, p.11.14-11.19
- J.A. Walsworth, P.J. Fehrenbach, and R. C. Spencer:
"Comparisons between ELOCA Code Calculations and CANDU Fuel Behaviour Under
LOCA Conditions", Proceedings of 6th CNS Annual Conference, June 1985,
p.11.28-11.35
- P.J. Fehrenbach, P.J., Hastings, I.J., Walsworth, J.A., Spencer, R.C.,
Lipsett, J.J., Hunt, C.E.L., Delaney, R.D.:
"Zircaloy-Sheathed UO2 Fuel Performance During In-Reactor LOCA Transients",
AECL-8569, 1984 October, Proceedings of Fifth International Meeting on Thermal
Nuclear Reactor Safety, 1984 September 9-13, Karlsruhe, West Germany
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NEA-1858/01
FIO-130_Report/ FIO-130_Report.txt in an ASCII file formatFIO-130_Tables/ 17 individual tables as ASCII files
FIO-130_Figures/ individual JPG and PNG versions of the figures
FIO-130_References/ references in PDF format
FIO-130_Ancillary_Data/ digitized data (Excel and ASCII files)
FIO-130.PDF combines the report, tables and figures
Keywords: CANDU, fuel behaviour, loss-of-coolant accident.